Light Water Reactor System Designed to Minimize Environmental Burden of Radioactive Waste
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Spent Nuclear Fuel Pools in the US
Spent Nuclear Fuel Pools in the U.S.: Reducing the Deadly Risks of Storage front cover WITH SUPPORT FROM: WITH SUPPORT FROM: By Robert Alvarez 1112 16th St. NW, Suite 600, Washington DC 20036 - www.ips-dc.org May 2011 About the Author Robert Alvarez, an Institute for Policy Studies senior scholar, served as a Senior Policy Advisor to the Secre- tary of Energy during the Clinton administration. Institute for Policy Studies (IPS-DC.org) is a community of public scholars and organizers linking peace, justice, and the environment in the U.S. and globally. We work with social movements to promote true democracy and challenge concentrated wealth, corporate influence, and military power. Project On Government Oversight (POGO.org) was founded in 1981 as an independent nonprofit that investigates and exposes corruption and other misconduct in order to achieve a more effective, accountable, open, and ethical federal government. Institute for Policy Studies 1112 16th St. NW, Suite 600 Washington, DC 20036 http://www.ips-dc.org © 2011 Institute for Policy Studies [email protected] For additional copies of this report, see www.ips-dc.org Table of Contents Summary ...............................................................................................................................1 Introduction ..........................................................................................................................4 Figure 1: Explosion Sequence at Reactor No. 3 ........................................................4 Figure 2: Reactor No. 3 -
Safety Analysis for Boiling Water Reactors
Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH Safety Analysis for Boiling Water Reactors A Summary GRS - 98 Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH Safety Analysis for Boiling Water Reactors A Summary E. Kersting J. von Linden D. Müller-Ecker W. Werner Translation by F. Janowski July 1993 GRS - 98 ISBN 3-923875-48-7 Note This report is the translation of GRS-95 "Sicherheitsanalyse für Siedewasserreaktoren - Zusammenfassende Darstellung". Recent analysis results - concerning the chapters on accident management, fire and earthquake - that were not included in the German text have been added to this translation. In cases of doubt, GRS-102 (main volume) is the factually correct version. Keywords Safety analysis, PSA, boiling water reactor, accidents, event-sequence analysis, systems analysis, fault-tree analysis, reliability data, accident management Abstract After completing the German Risk Study for pressurised water reactors, the Gesell schaft für Anlagen- und Reaktorsicherheit (GRS) has now conducted for the first time a probabilistic safety analysis for boiling water reactors (BWR) on behalf of the Federal Minister for Research and Technology (BMFT). Reactor safety is constantly developed in line with research findings and operating experience. Thus reactor safety is a dynamic process in which safety analyses play an important role. Probabilistic safety analyses determine the frequency of certain events (e.g. leaks in pipes) and the failure probabilities of the safety systems needed to control such events. The failure of safety systems initially leads to a hazard to the cooling of the reactor core. When such hazard states occur, there are accident management measures which can still be carried out in order to prevent core melt. -
Self-Sustaining Thorium Boiling Water Reactors
Project No. 11-3023 Self-Sustaining Thorium Boiling Water Reactors Reactor Concepts Dr. Ehud Greenspan University of California-Berkeley In collaboration with: Massachusetts Institute of Technology University of Michigan Brookhaven National Laboratory Brian Robinson, Federal POC Temitope Taiwo, Technical POC NEUP Project # 11-3023 September 2011 to December 2014 Self-sustaining thorium boiling water reactors Summary Report Ehud Greenspan, Phillip M. Gorman, Sandra Bogetic, Jeffrey E. Seifried, Guanheng Zhang, Christopher R. Varela, Massimiliano Fratoni and Jasmina L. Vujic UC Berkeley, [email protected] Thomas Downar, Andrew Hall, Andrew Ward, Michael Jarrett, Aaron Wysocki and Yunlin Xu University of Michigan, [email protected] Mujid Kazimi, Koroush Shirvan and Alexander Mieloszyk MIT, [email protected] Michael Todosow, Nicholas Brown and Lap Cheng BNL, [email protected] 28 February 2015 1 Table of Contents Overview Page Executive summary 3 1. Introduction 7 2. The RBWR cores 7 2.1 Hitachi RBWR cores 7 2.2 Independent evaluation of the Hitachi designs 14 2.3 The incentive for thorium-based RBWR 15 2.4 The thorium-based RBWR core designs 17 3. Development of computational methods for RBWR type cores 19 3.1 3-D core simulator 20 3.2 Monte-Carlo based coupled neutronics - TH - depletion analysis capability 21 3.3 Stability and safety analysis capability 21 3.4 Fuel performance analysis capability 22 3.5 Thermal hydraulic correlations for tight lattice high void cores 24 4. Feasibility of fuel-self-sustaining RBWR-Th cores 24 4.1 Study strategy 24 4.2 RBWR-Th core designs 26 4.3 RBWR-Th safety and stability 30 4.4 RBWR-Th fuel performance 31 5. -
Possibility of Deuteron Disintegration in Condensed Matter, a Review
POSSIBILITY OF DEUTERON DISINTEGRATION IN CONDENSED MATTER, A REVIEW © M. Ragheb 1/16/2021 “Discovery consists of seeing what everyone has seen, and thinking what no one has thought.” Albert Szent-Gyorgi, 1937 Nobel Laureate in Physio;ogy/ Medicine “If we all worked on the assumption that what is accepted as true is really true, There would be little hope of advance.” Orville Wright "I may disagree with what you say but will defend to the death your right to say it." Voltaire, French writer, philosopher and historian “La vérité est en marche, et rien ne l’arrêtera.” Emile Zola “Rien ne peut arrêter une idée don’t l’heure est venue.” Victor Hugo “We wish to pursue the truth, no matter where it leads. But to find the truth, we need imagination and skepticism, both. We will not be afraid to speculate, but we will be careful to distinguish speculation from fact.” “Absence of evidence is not evidence of absence.” Carl Sagan, Astronomer, ‘Cosmos’ “The miracle is not how well the bear waltzes, but that it can waltz at all.” PT Barnum “There is only one way to avoid criticism: do nothing, say nothing, and be nothing.” Aristotle. Greek philosopher “I've missed more than 9,000 shots in my career. I've lost almost 300 games. Twenty six times, I've been trusted to take the game winning shot and missed. I've failed over and over and over again in my life. And that is why I succeed.” Michael Jordan, USA Basketball Champion “It ain't what you don't know that gets you into trouble. -
Doe Nuclear Physics Reactor Theory Handbook
DOE-HDBK-1019/2-93 JANUARY 1993 DOE FUNDAMENTALS HANDBOOK NUCLEAR PHYSICS AND REACTOR THEORY Volume 2 of 2 U.S. Department of Energy FSC-6910 Washington, D.C. 20585 Distribution Statement A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831. Available to the public from the National Technical Information Service, U.S. Department of Commerce, 5285 Port Royal., Springfield, VA 22161. Order No. DE93012223 DOE-HDBK-1019/1-93 NUCLEAR PHYSICS AND REACTOR THEORY ABSTRACT The Nuclear Physics and Reactor Theory Handbook was developed to assist nuclear facility operating contractors in providing operators, maintenance personnel, and the technical staff with the necessary fundamentals training to ensure a basic understanding of nuclear physics and reactor theory. The handbook includes information on atomic and nuclear physics; neutron characteristics; reactor theory and nuclear parameters; and the theory of reactor operation. This information will provide personnel with a foundation for understanding the scientific principles that are associated with various DOE nuclear facility operations and maintenance. Key Words: Training Material, Atomic Physics, The Chart of the Nuclides, Radioactivity, Radioactive Decay, Neutron Interaction, Fission, Reactor Theory, Neutron Characteristics, Neutron Life Cycle, Reactor Kinetics Rev. 0 NP DOE-HDBK-1019/1-93 NUCLEAR PHYSICS AND REACTOR THEORY FOREWORD The Department of Energy (DOE) Fundamentals Handbooks consist of ten academic subjects, which include Mathematics; Classical Physics; Thermodynamics, Heat Transfer, and Fluid Flow; Instrumentation and Control; Electrical Science; Material Science; Mechanical Science; Chemistry; Engineering Symbology, Prints, and Drawings; and Nuclear Physics and Reactor Theory. -
Report on Technical Feasibility of Fusion Energy to the Special Committee for the ITER Project
March 8, ASDEX Upgrade Seminar Report on Technical Feasibility of Fusion Energy to the Special Committee for the ITER Project M. Kikuchi Former member of subcommittee for Fusion Development Strategy under Fusion Council Structure of Fusion Program Promotion in Japan (before May 17,2000) Special committee for the ITER Project Chair: Prof. H. Yoshikawa Atomic Energy Fusion ITER/EDA Technical Commission Council Subcommittee Chair: Prof. N. Inoue Chair: Prof. M. Wakatani Planning and Promotion Subcommittee Chair: Prof. K. Miya Subcommittee for Fusion Development Strategy Chair: Prof. N. Inoue 1 Charge to Subcommittee for Fusion Development Strategy (3) Technical feasibility of the fusion energy (4) Extension of the program and basic supporting research For topic (3) above, the Special Committee additionally requested an evaluation of the feasibility of fusion energy as a safe and reliable energy source from the aspects of technical potential, management capability, and characteristics of Japanese industrial structure. Two other subcommittes are formed for answering (1) Survey of long term demand and supply of energy sources (2) Feasibility study of alternative energy sources (5) Distribution of resources for research (6) International relations. 2 Members of Subcommittee for Fusion Development Strategy (April 2000) Nobuyuki Inoue (Chairman) Chairman of Fusion Council Professor, Institute of Advanced Energy, Kyoto University) Katsunori Abe Professor, Graduate School of Engineering, Tohoku University Kunihiko Okano Research Fellow, Komae Research -
Progress in Nuclear Energy 105 (2018) 83–98
Progress in Nuclear Energy 105 (2018) 83–98 Contents lists available at ScienceDirect Progress in Nuclear Energy journal homepage: www.elsevier.com/locate/pnucene Technology perspectives from 1950 to 2100 and policy implications for the T global nuclear power industry Victor Nian Energy Studies Institute, National University of Singapore, Singapore ARTICLE INFO ABSTRACT Keywords: There have been two completed phases of developments in nuclear reactor technologies. The first phase is the Nuclear industry trends demonstration of exploratory Generation I reactors. The second phase is the rapid scale-up of Generation II Nuclear energy policy reactors in North America and Western Europe followed by East Asia. We are in the third phase, which is the ff Technology di usion construction of evolutionary Generation III/III+ reactors. Driven by the need for safer and more affordable New user state nuclear reactors post-Fukushima, the nuclear industry has, in parallel, entered the fourth phase, which is the International cooperation development of innovative Generation IV reactors. Through a comprehensive review of the historical reactor Advanced reactor development technology developments in major nuclear states, namely, USA, Russia, France, Japan, South Korea, and China, this study presents a projection on the future potentials of advanced reactor technologies, with particular focus on pressurized water reactors, high temperature reactors, and fast reactors, by 2100. The projected potentials provide alternative scenarios to develop insights that complement the established technology roadmaps. Findings suggest that there is no clear winner among these technologies, but fast reactors could demonstrate a new and important decision factor for emerging markets. Findings also suggest small modular reactors, espe- cially those belonging to Generation IV, as a transitional technology for developing domestic market and in- digenous technology competence for emerging nuclear states. -
A Comparison of Advanced Nuclear Technologies
A COMPARISON OF ADVANCED NUCLEAR TECHNOLOGIES Andrew C. Kadak, Ph.D MARCH 2017 B | CHAPTER NAME ABOUT THE CENTER ON GLOBAL ENERGY POLICY The Center on Global Energy Policy provides independent, balanced, data-driven analysis to help policymakers navigate the complex world of energy. We approach energy as an economic, security, and environmental concern. And we draw on the resources of a world-class institution, faculty with real-world experience, and a location in the world’s finance and media capital. Visit us at energypolicy.columbia.edu facebook.com/ColumbiaUEnergy twitter.com/ColumbiaUEnergy ABOUT THE SCHOOL OF INTERNATIONAL AND PUBLIC AFFAIRS SIPA’s mission is to empower people to serve the global public interest. Our goal is to foster economic growth, sustainable development, social progress, and democratic governance by educating public policy professionals, producing policy-related research, and conveying the results to the world. Based in New York City, with a student body that is 50 percent international and educational partners in cities around the world, SIPA is the most global of public policy schools. For more information, please visit www.sipa.columbia.edu A COMPARISON OF ADVANCED NUCLEAR TECHNOLOGIES Andrew C. Kadak, Ph.D* MARCH 2017 *Andrew C. Kadak is the former president of Yankee Atomic Electric Company and professor of the practice at the Massachusetts Institute of Technology. He continues to consult on nuclear operations, advanced nuclear power plants, and policy and regulatory matters in the United States. He also serves on senior nuclear safety oversight boards in China. He is a graduate of MIT from the Nuclear Science and Engineering Department. -
Self-Sustaining Thorium Boiling Water Reactors
Project No. 11-3023 Self-Sustaining Thorium Boiling Water Reactors Reactor Concepts Dr. Ehud Greenspan University of California-Berkeley In collaboraon with: Massachuses Instute of Technology University of Michigan Brookhaven Naonal Laboratory Brian Robinson, Federal POC Temitope Taiwo, Technical POC NEUP Project # 11-3023 September 2011 to December 2014 Self-sustaining thorium boiling water reactors Summary Report Ehud Greenspan, Phillip M. Gorman, Sandra Bogetic, Jeffrey E. Seifried, Guanheng Zhang, Christopher R. Varela, Massimiliano Fratoni and Jasmina L. Vujic UC Berkeley, [email protected] Thomas Downar, Andrew Hall, Andrew Ward, Michael Jarrett, Aaron Wysocki and Yunlin Xu University of Michigan, [email protected] Mujid Kazimi, Koroush Shirvan and Alexander Mieloszyk MIT, [email protected] Michael Todosow, Nicholas Brown and Lap Cheng BNL, [email protected] 28 February 2015 1 Table of Contents Overview Page Executive summary 3 1. Introduction 7 2. The RBWR cores 7 2.1 Hitachi RBWR cores 7 2.2 Independent evaluation of the Hitachi designs 14 2.3 The incentive for thorium-based RBWR 15 2.4 The thorium-based RBWR core designs 17 3. Development of computational methods for RBWR type cores 19 3.1 3-D core simulator 20 3.2 Monte-Carlo based coupled neutronics – TH – depletion analysis capability 21 3.3 Stability and safety analysis capability 21 3.4 Fuel performance analysis capability 22 3.5 Thermal hydraulic correlations for tight lattice high void cores 24 4. Feasibility of fuel-self-sustaining RBWR-Th cores 24 4.1 Study strategy 24 4.2 RBWR-Th core designs 26 4.3 RBWR-Th safety and stability 30 4.4 RBWR-Th fuel performance 31 5. -
Fundamentals of Nuclear Power
Fundamentals of Nuclear Power Juan S. Giraldo Douglas J. Gotham David G. Nderitu Paul V. Preckel Darla J. Mize State Utility Forecasting Group December 2012 Table of Contents List of Figures .................................................................................................................................. iii List of Tables ................................................................................................................................... iv Acronyms and Abbreviations ........................................................................................................... v Glossary ........................................................................................................................................... vi Foreword ........................................................................................................................................ vii 1. Overview ............................................................................................................................. 1 1.1 Current state of nuclear power generation in the U.S. ......................................... 1 1.2 Nuclear power around the world ........................................................................... 4 2. Nuclear Energy .................................................................................................................... 9 2.1 How nuclear power plants generate electricity ..................................................... 9 2.2 Radioactive decay ................................................................................................. -
VVER-1000 Coolant Transient Benchmark
Nuclear Science NEA/NSC/DOC(2002)6 VVER-1000 Coolant Transient Benchmark PHASE 1 (V1000CT-1) Vol. I: Main Coolant Pump (MCP) switching On – Final Specifications Boyan Ivanov and Kostadin Ivanov Nuclear Engineering Program, USA Pavlin Groudev and Malinka Pavlova INRNE, Academy of Sciences, Bulgaria Vasil Hadjiev Nuclear Power Plant Kozloduy, Bulgaria US Department of Energy NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT Pursuant to Article 1 of the Convention signed in Paris on 14th December 1960, and which came into force on 30th September 1961, the Organisation for Economic Co-operation and Development (OECD) shall promote policies designed: − to achieve the highest sustainable economic growth and employment and a rising standard of living in Member countries, while maintaining financial stability, and thus to contribute to the development of the world economy; − to contribute to sound economic expansion in Member as well as non-member countries in the process of economic development; and − to contribute to the expansion of world trade on a multilateral, non-discriminatory basis in accordance with international obligations. The original Member countries of the OECD are Austria, Belgium, Canada, Denmark, France, Germany, Greece, Iceland, Ireland, Italy, Luxembourg, the Netherlands, Norway, Portugal, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. The following countries became Members subsequently through accession at the dates indicated hereafter: Japan (28th April 1964), Finland (28th January 1969), Australia (7th June 1971), New Zealand (29th May 1973), Mexico (18th May 1994), the Czech Republic (21st December 1995), Hungary (7th May 1996), Poland (22nd November 1996), Korea (12th December 1996) and the Slovak Republic (14 December 2000). -
Responds to NRC 840504 Ltr Re Violations Noted in IE
- , . , . Georgia Institute of Technology SCHOOL OF NUCLEAR ENGINEERING AND HEALTH PHYSICS R ATLANTA. GEORGIA 30332 ' & " ' NEELY NUCLEAR RESEAACH e (404)094-3800 CENTER May 25, 1984 Mr. David M. Verrelli, Chief Reactor Projects Branch U.S. Nuclear Regulatory Commission, Region II 101 Marietta Street, N.W. Atlanta, Georgia 30303 Subject: Inspection Report No. 50-276/84-02 | Dear Mr. Verrelli: | This letter is my response to the referenced inspection of the Georgia Tech AGN-201 reactor on April 11-12, 1984. 1 Enclosed is a copy of the Dismantling and Disposal Plan for I the AGN-201 which I sent to Mr. Cecil 0. Thomas of NRC for ! approval. This plan was reviewed and approved by the I.uclear Safeguards Committee of Georgia Tech (see appended letter). Immediately following approval of this plan by NRC, Georgia Tech will proceed to dismantle and dispose of the AGN-201. Item: The proposed emergency plan has not been appro- priately revised to reflect changes in the onsite emergency response organization for the AGN-201. The revised emergency procedures for the AGN-201 are appended. The telephone numbers of the emetgency director and all support organizations ..ce now available in the Nuclear Engineering Program Office. Item: No radiological exercise has been conducted since September 9, 1980 when Grady Meuorial llospital participated with the licensee in a drill involving a simulated personnel contamination problem. An emergency drill involving personnel contamination problem 1lospital.is being planned for the summer of 1984 in conjunction with Grady Item: Update agreement with Grady llospital and provide l'n emergency plan for biennial review and periodic update.